JPS61292599A - Vessel for radioactive waste - Google Patents

Vessel for radioactive waste

Info

Publication number
JPS61292599A
JPS61292599A JP13427385A JP13427385A JPS61292599A JP S61292599 A JPS61292599 A JP S61292599A JP 13427385 A JP13427385 A JP 13427385A JP 13427385 A JP13427385 A JP 13427385A JP S61292599 A JPS61292599 A JP S61292599A
Authority
JP
Japan
Prior art keywords
container
radioactive waste
waste
detector
solidified
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
JP13427385A
Other languages
Japanese (ja)
Inventor
勝也 内田
正俊 川島
克彦 中原
角田 章男
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Nippon Atomic Industry Group Co Ltd
Original Assignee
Toshiba Corp
Nippon Atomic Industry Group Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Toshiba Corp, Nippon Atomic Industry Group Co Ltd filed Critical Toshiba Corp
Priority to JP13427385A priority Critical patent/JPS61292599A/en
Publication of JPS61292599A publication Critical patent/JPS61292599A/en
Pending legal-status Critical Current

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  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)
  • Processing Of Solid Wastes (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は例えば使用済燃料再処理後の廃棄物等の放射性
廃棄物をセメント同化体、ガラス同化体等として密封管
理するための放射性廃棄物用容器に関する。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a radioactive waste product for sealed management of radioactive waste such as waste after spent fuel reprocessing as cement assimilated material, glass assimilated material, etc. Regarding containers.

(発明の技術的背景とその問題点〕 使用済燃料を再処理した後の廃棄物はpu、cm等の中
性子、α線を放出する重核を含むため、半減期が長く、
有害性の物質を有するのでその管理が重要である。廃棄
物内のこれらの核種を定量する方法として、第4図に示
すように廃棄物固化体用の容器Aを囲むポリエチレン等
の材質からなる側壁1の内部に複数の孔を設け、これら
の孔に中性子検出器3を挿入設置し、廃棄物固化体から
放出される中性子を測定するパッシブ中性子法がある。
(Technical background of the invention and its problems) The waste after reprocessing spent fuel contains heavy nuclei that emit neutrons and alpha rays, such as PU and cm, so it has a long half-life.
Since it contains hazardous substances, its management is important. As a method for quantifying these nuclides in waste, as shown in Fig. 4, a plurality of holes are provided inside a side wall 1 made of a material such as polyethylene that surrounds a container A for solidified waste, and these holes are There is a passive neutron method in which a neutron detector 3 is inserted into the waste material and neutrons emitted from the solidified waste are measured.

この方法は中性子検出器3に近い廃棄物同化体から放出
する中性子発生量を検出するには適している。しかしな
がら、中性子検出器3の感度に対する中性子線源位置の
関係を示す第5図から明らかなように容器中心位置側の
領域になるにつれてpu、cm等のα放射能の定量は精
度が極めて悪くなる。また、廃棄物固化体の単核が偏在
している場合には廃棄物固化体内の単核の定量化の精度
が極めて低い問題がある。
This method is suitable for detecting the amount of neutrons emitted from the waste assimilate near the neutron detector 3. However, as is clear from FIG. 5, which shows the relationship between the sensitivity of the neutron detector 3 and the position of the neutron source, the accuracy of quantifying alpha radioactivity such as pu and cm becomes extremely poor as the area approaches the center of the container. . In addition, when mononuclei in the solidified waste are unevenly distributed, there is a problem in which the accuracy of quantifying the mononuclear in the solidified waste is extremely low.

〔発明の目的〕[Purpose of the invention]

本発明の目的は、使用済燃料を再処理した後の廃棄物等
の放射性廃棄物をセメント固化体、ガラス固化体等の固
化体として容器に密封管理するに際して、放射性廃棄物
からの中性子等の放射線を精度よく検出して放射性廃棄
物を安全に管理できる放射性廃棄物用容器を提供するこ
とにある。
The purpose of the present invention is to prevent neutrons, etc. from radioactive waste when managing radioactive waste, such as waste after reprocessing spent fuel, as a cement solidified material, vitrified material, etc. in a sealed container. An object of the present invention is to provide a container for radioactive waste that can accurately detect radiation and safely manage radioactive waste.

〔発明の概要〕[Summary of the invention]

本発明は、放射性廃棄物固化体を密封する放射性廃棄物
容器において、この容器面から少なくとも前記同化体に
くい込む放射線検出器設置用の空間部を固化体に対する
外部からの密封性を保持した状態で設けたことを特徴と
する放射性廃棄物用容器である。
The present invention provides a radioactive waste container for sealing a solidified radioactive waste, in which at least a space for installing a radiation detector into which the assimilated material is embedded from the surface of the container is kept sealed from the outside with respect to the solidified material. This is a container for radioactive waste characterized by the following:

〔発明の実施例〕[Embodiments of the invention]

以下、本発明の実施例を図面に基づいて説明する。 Embodiments of the present invention will be described below based on the drawings.

第1図は本発明に係る放射性廃棄物用容器を示す斜視図
、第2図は第1図のA−A線に沿う断面図である。
FIG. 1 is a perspective view showing a radioactive waste container according to the present invention, and FIG. 2 is a sectional view taken along line A-A in FIG. 1.

第1図および第2図において、容器5内には使用済燃料
を再処理した後の放射性廃棄物の固化体が充填されてい
る。容器5はその底面に容器5の高さ方向に延設され、
それぞれ所定の間隔をおいて3個の空間部6が形成され
ている。この空間部6はそれぞれ容器5の密封性を保持
した状態で設けられている。これらの空間部6にそれぞ
れ中性子検出器7が設置される。このような放射性廃棄
物用容器において、中性子検出器7は放射性廃棄物5の
固化体のほぼ中心領域およびその周辺領域に設置されて
いる。第3図は容器5の中心からの距離と中性子検出器
7による感度との関係を示す。
1 and 2, a container 5 is filled with solidified radioactive waste after reprocessing spent fuel. The container 5 has a bottom surface extending in the height direction of the container 5,
Three spaces 6 are formed at predetermined intervals. The spaces 6 are each provided in a state in which the container 5 is kept sealed. A neutron detector 7 is installed in each of these spaces 6. In such a container for radioactive waste, the neutron detector 7 is installed approximately in the central area of the solidified body of radioactive waste 5 and in the surrounding area. FIG. 3 shows the relationship between the distance from the center of the container 5 and the sensitivity of the neutron detector 7.

第3図から明らかなように容器5の中心領域では感度が
高く、容器5の中心領域から容器5の側壁になるにつれ
て感度は低下するが、その低下の割合は極めて少ない。
As is clear from FIG. 3, the sensitivity is high in the center region of the container 5, and the sensitivity decreases from the center region of the container 5 toward the side wall of the container 5, but the rate of decrease is extremely small.

本実施例では、空間部6として3個の柱状空間部の例を
示しているが空間部の個数は固化体の大ぎさによって任
意に選定することができる。また空間部は容器の底面か
ら容器の高さ方向に延設されたものに限定される訳でな
く、容器の側壁から容器の軸方向側に延設してもよい。
In this embodiment, an example of three columnar spaces is shown as the space 6, but the number of spaces can be arbitrarily selected depending on the size of the solidified body. Furthermore, the space is not limited to extending from the bottom of the container in the height direction of the container, but may extend from the side wall of the container in the axial direction of the container.

さらに第3図に示すような空間部とともに第1図に示し
たような容器の側壁に複数個の中性子検出器用孔を設け
、それらの孔に中性子検出器を設置してもよい。この場
合、第2図と第5図に示す感度曲線を合成した感度曲線
が得られ、固化体内のPu、Cm等の分布の偏りにかか
わらず中性子の定fft1度がさらに向上する。
Furthermore, a plurality of neutron detector holes may be provided in the side wall of the container as shown in FIG. 1 together with the space shown in FIG. 3, and the neutron detectors may be installed in these holes. In this case, a sensitivity curve is obtained by combining the sensitivity curves shown in FIGS. 2 and 5, and the neutron constant fft1 degree is further improved regardless of the bias in the distribution of Pu, Cm, etc. in the solidified body.

本発明において空間部に設置される検出器は中性子検出
器に限らず、放射性廃棄物から放出される放射線を検出
できるものであればよい。また、放射性廃棄物は核燃料
の再処理廃棄物に限らず、容器内に固化体として収納さ
れるものであればよい。
In the present invention, the detector installed in the space is not limited to a neutron detector, but may be any detector that can detect radiation emitted from radioactive waste. Moreover, the radioactive waste is not limited to nuclear fuel reprocessing waste, but may be any waste that can be stored as a solidified substance in a container.

〔発明の効梁〕[Effect beam of invention]

以上のように本発明によれば、放射性廃棄物の固化体か
ら放出される中性子、γ線等を感度よく検出することが
でき、また固化体が大型の場合にも線源領域付近に検出
器が設置されるので中性子、γ線等の検出により″単核
定量化の精度を高めることができる。
As described above, according to the present invention, it is possible to detect neutrons, gamma rays, etc. emitted from solidified bodies of radioactive waste with high sensitivity, and even when the solidified body is large, a detector is placed near the radiation source area. Since a detector is installed, the accuracy of mononuclear quantification can be improved by detecting neutrons, gamma rays, etc.

【図面の簡単な説明】[Brief explanation of drawings]

第1図は本発明に係る放射性廃棄物用容器を一部透視で
示す斜視図、第2図は第1図へ−A線に沿う断面図、第
3図は第1図の容器における容器中心領域からの距離と
検出器の感度との関係を示すグラフ、第4図は従来の放
射性廃棄物用容器の容器を一部透視で示す要部斜視図、
第5図は第4図の容器における容器中心領域からの距離
と検出器の感度との関係を示すグラフである。 1・・・容器側壁、2・・・孔、3・・・中性子検出器
、5・・・容器、6・・・空間部、7・・・中性子検出
器。 第 2 図 茶4ヨ       第5図
Fig. 1 is a partially transparent perspective view of a container for radioactive waste according to the present invention, Fig. 2 is a sectional view taken along the line A to Fig. 1, and Fig. 3 is the center of the container in Fig. 1. A graph showing the relationship between the distance from the area and the sensitivity of the detector; FIG. 4 is a perspective view of the main parts of a conventional radioactive waste container partially transparent;
FIG. 5 is a graph showing the relationship between the distance from the center region of the container in FIG. 4 and the sensitivity of the detector. DESCRIPTION OF SYMBOLS 1... Container side wall, 2... Hole, 3... Neutron detector, 5... Container, 6... Space part, 7... Neutron detector. 2nd diagram Tea 4yo Figure 5

Claims (1)

【特許請求の範囲】 1、放射性廃棄物の固化体を密封する放射性廃棄物用容
器において、この容器面から少なくとも前記固化体にく
い込む放射線検出器設置用の空間部を固化体に対する外
部からの密封性を保持した状態で設けたことを特徴とす
る放射性廃棄物用容器。 2、放射線検出器が、中性子検出器である特許請求の範
囲第1項記載の放射性廃棄物用容器。 3、放射性廃棄物が、核燃料を再処理した後の廃棄物で
ある特許請求の範囲第1項記載の放射性廃棄物用容器。
[Claims] 1. In a radioactive waste container for sealing a solidified body of radioactive waste, at least a space for installing a radiation detector that is embedded in the solidified body from the surface of the container is sealed from the outside with respect to the solidified body. A container for radioactive waste characterized by being provided in a state where its properties are maintained. 2. The radioactive waste container according to claim 1, wherein the radiation detector is a neutron detector. 3. The radioactive waste container according to claim 1, wherein the radioactive waste is waste after reprocessing nuclear fuel.
JP13427385A 1985-06-21 1985-06-21 Vessel for radioactive waste Pending JPS61292599A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP13427385A JPS61292599A (en) 1985-06-21 1985-06-21 Vessel for radioactive waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP13427385A JPS61292599A (en) 1985-06-21 1985-06-21 Vessel for radioactive waste

Publications (1)

Publication Number Publication Date
JPS61292599A true JPS61292599A (en) 1986-12-23

Family

ID=15124427

Family Applications (1)

Application Number Title Priority Date Filing Date
JP13427385A Pending JPS61292599A (en) 1985-06-21 1985-06-21 Vessel for radioactive waste

Country Status (1)

Country Link
JP (1) JPS61292599A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2015190761A (en) * 2014-03-27 2015-11-02 日立Geニュークリア・エナジー株式会社 storage container of radioactive material

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2015190761A (en) * 2014-03-27 2015-11-02 日立Geニュークリア・エナジー株式会社 storage container of radioactive material

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